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Relevant bibliographies by topics / Radioactive gages

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Academic literature on the topic 'Radioactive gages'

Author: Grafiati

Published: 4 June 2021

Last updated: 16 February 2022

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Journal articles on the topic "Radioactive gages"

1

Poluéktov, P. P., and L. N. Rastunov. "Nonstationary chromatography of radioactive gases." Atomic Energy 81, no. 3 (1996): 629–31. http://dx.doi.org/10.1007/bf02407054.

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Baek, Inseok, and John W. Poston. "A DOSIMETRIC MODEL FOR INHALED RADIOACTIVE GASES." Health Physics 79, no. 2 (2000): 162–69. http://dx.doi.org/10.1097/00004032-200008000-00009.

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Querfeld, Rebecca, Mayumi Hori, Anica Weller, Detlev Degering, Katsumi Shozugawa, and Georg Steinhauser. "Radioactive Games? Radiation Hazard Assessment of the Tokyo Olympic Summer Games." Environmental Science & Technology 54, no. 18 (2020): 11414–23. http://dx.doi.org/10.1021/acs.est.0c02754.

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Gavcrilin, Yu I., U. Ya Margulis, and V. T. Khrushch. "Cryogenic sampler for collecting radioactive gases and aerosols." Measurement Techniques 29, no. 5 (1986): 478–82. http://dx.doi.org/10.1007/bf00865965.

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Howard, A. J., and W. P. Strange. "Prototypical search for radioactive superheavy elements in gases." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 325, no. 1-2 (1993): 224–33. http://dx.doi.org/10.1016/0168-9002(93)91024-h.

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Akerib, D. S., H. M. Araújo, X. Bai, et al. "Chromatographic separation of radioactive noble gases from xenon." Astroparticle Physics 97 (January 2018): 80–87. http://dx.doi.org/10.1016/j.astropartphys.2017.10.014.

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Osada, N., Y. Oki, H. Kanda, K. Yamasaki, and S. Shibata. "Application of a graded screen array for size measurements of radioactive aerosols in accelerator rooms." Proceedings in Radiochemistry 1, no. 1 (2011): 251–55. http://dx.doi.org/10.1524/rcpr.2011.0044.

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Abstract A rapid measurement method for aerosol particle size is required to clarify the formation mechanism of freshly-formed radioactive aerosols in accelerator rooms. A graded screen array (GSA) method only requires brief sampling. Therefore, the GSA method is suitable for the measurement of radioactive aerosols in the accelerator rooms. In this work, a conventional GSA was applied to measure the particle size distribution of an aerosol. An influence of the radioactive gas on the GSA measurement was found. The adsorption of radioactive gases resulted in a discrepancy between the results of the GSA method and those of the diffusion battery method. An improved GSA method was developed to measure the radioactive aerosol formed in the accelerator room. The adsorption was measured by the improved GSA, and the influence of the radioactive gas was eliminated. The result of the improved GSA showed fair agreement with that of the diffusion battery system.

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Kalinichev, Peter, Igor Evdokimov, and Vladimir Likhanskii. "A technique for detection of WWER fuel failures by activity of Xe radionuclides during reactor operation." Nuclear Energy and Technology 4, no. 4 (2018): 263–70. http://dx.doi.org/10.3897/nucet.4.31889.

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Fuel failures during operation of Nuclear Power Plants (NPPs) may lead to substantial economic losses. Negative effects of reactor operation with leaking fuel in the core may be reduced if fuel failures are detected in due time of the cycle. At present time, the ratio of the normalized release rates of 131I and 134I is used to detect fuel failures in WWERs during steady state operation. However, based on the activity of iodine radionuclides, it is not always possible to detect the fuel failure. This situation may occur in case of a small defect in cladding of a leaking fuel rod or for high burnup fuel if the defect is overlapped by the surface of the fuel pellet. If it is so, fuel deposits may be the dominant contributor to iodine activity, and the fuel failure may not be noticeable. In PWRs, fuel failures are detected by activity of radioactive noble gases. Noble gases are not adsorbed on cladding inner surface, as distinct from iodine radionuclides. Release of noble gases from the leaking fuel rod may be considerable even though defect in cladding is small. In this paper, a technique is proposed for detection of fuel failures at WWER reactors by activity of radioactive noble gases in the primary coolant. It is shown that radioactive noble gases may be a more sensitive indicator of fuel failures than iodine radionuclides. Detection of fuel failures is based on monitoring of the ratio between 133Xe and 135Xe activity. Some examples of practical applications are given.

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Liprie, Samuel F. "The Nuclear Pharmacist as a Radiation Safety Officer." Journal of Pharmacy Practice 2, no. 5 (1989): 276–79. http://dx.doi.org/10.1177/089719008900200503.

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The Radiation Safety Officer (RSO) is responsible for the safety of the staff, visitors, and patients who may work with, or come into contact with, radioactive materials. This responsibility often calls for establishing and enforcing radiation safety policies and procedures. The position of the RSO may have even greater dimensions at facilities where medical research uses radioactive materials or where radioactive sources are being implanted in cancer patients for therapy. Since the nuclear pharmacist handles radioactive solids, liquids, and/or gases on a daily basis, his knowledge and experience ideally qualify him to perform the duties of an RSO. Those duties and responsibilities include, but are not limited to, monitoring for environmental safety and personnel radiation exposure, monitoring of incoming and outgoing radioactive shipments, and verification that all record-keeping activities, possession quantities, and uses of radioactive material are in keeping with the facility's radioactive material license. Basically, the RSO is responsible for the safe use of any radioactive material from the time it arrives until the time it is removed for waste disposal. The following article reviews some of the duties of the RSO, and shows how easily the nuclear pharmacist can assume this role.

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Kuzhevskij, B. M., O. Yu Nechaev, E. A. Sigaeva, and V. A. Zakharov. "Neutron flux variations near the Earth’s crust. A possible tectonic activity detection." Natural Hazards and Earth System Sciences 3, no. 6 (2003): 637–45. http://dx.doi.org/10.5194/nhess-3-637-2003.

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Abstract. The present work contains some results of observations of neutron flux variations near the Earth’s surface. The Earth’s crust is determined to be a significant source of thermal and slow neutrons, originated from the interaction between the nuclei of the elements of the Earth’s crust and the atmosphere and α-particles, produced by decay of radioactive gases (Radon, Thoron and Actinon). In turn, variations of radioactive gases exhalation is connected with geodynamical processes in the Earth’s crust, including tectonic activity. This determined relation between the processes in the Earth’s crust and neutrons’ flux allow to use variations of thermal and slow neutrons’ flux in order to observe increasing tectonic activity and to develop methods for short-term prediction of natural hazards.

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Dissertations / Theses on the topic "Radioactive gages"

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Alattar, Iyad Ahmed. "Evaluation of Troxler 3241-C nuclear asphalt content gauge used for Marshall specimens." Thesis, This resource online, 1994. http://scholar.lib.vt.edu/theses/available/etd-12042009-020138/.

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Standing, Eamon Daniel. "Design and fabrication of high magnetic field gradients towards fault tolerant two-qubit gates with trapped ions using long-wavelength radiation." Thesis, University of Sussex, 2017. http://sro.sussex.ac.uk/id/eprint/69336/.

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In this thesis, I discuss coherent manipulation of a trapped ytterbium ion using long wavelength radiation and the results of experiments towards the performance of a two-ion entanglement gate using a static magnetic field gradient of 23.3(6) T/m to create coupling between an ion's internal state and its motion. After using these experiments to explain the requirements for high-fidelity entanglement operations, I continue by examining existing methods for creating this gradient, the current limiting factor in producing the highest fidelity operations. This includes a full characterisation of the gradients produced by symmetric scheme permanent magnets and buried current carrying wires including development of scaling laws in order to create optimum gradients for a given trap geometry. I continue by proposing a new method by which extremely high gradients over 100 T/m can be created for planar chip traps with minimal modification to an existing experiment. These gradients are tailored for axial as well as radial entanglement schemes and aim to show that the technology exists in order to produce a two-qubit gate over the fault tolerant threshold. Subsequently, I discuss the implementation of this new scheme in an experiment before constructing the apparatus to accurately align a chip with these magnets and documenting their installation into two new experimental setups. This includes a preliminary measurement of the gradient produced by an imperfect setup outside of vacuum which verifies those simulated at ~ 110 T/m. Lastly, I discuss the prospects of on-chip magnetic materials and propose a new method which when sufficiently developed should allow for high magnetic field gradients to be produced on-chip at higher ion heights than when solely using current carrying wires. Additionally this scheme should allow for switchable gradients with maximised stability in geometries previously not possible to create.

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Morlando, Rebecca A. "Chemchar gasification of metal-bearing wastes, chlorinated organics and doe surrogate wastes /." free to MU campus, to others for purchase, 1997. http://wwwlib.umi.com/cr/mo/fullcit?p9841325.

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COSTA, RENATA F. da. "Sensoriamento remoto a laser de aerossóis em uma refinaria de petróleo." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/26387.

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Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2016-06-22T13:39:10Z No. of bitstreams: 0<br>Made available in DSpace on 2016-06-22T13:39:10Z (GMT). No. of bitstreams: 0<br>Fundação de Amparo à Pesquisa do Estado de São Paulo (FAPESP)<br>Tese (Doutorado em Tecnologia Nuclear)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP<br>FAPESP:11/00769-7

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Smith, Thomas. "Transfert vertical des gaz rares à l'échelle des différentes formations de la zone de transposition du site Meuse/Haute-Marne et à l'échelle des eaux porales de l'argilite du Callovo-Oxfordien." Thesis, Bordeaux 1, 2010. http://www.theses.fr/2010BOR14127/document.

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L’Agence nationale pour la gestion des déchets radioactifs (Andra) a pour mission d’évaluer la possibilité d’un stockage sûr et réversible des déchets de haute activité et à vie longue (HAVL) en milieu géologique profond. Depuis 1994, l’Andra étudie dans cette optique les propriétés d’une couche argileuse, le Callovo-Oxfordien (COx) située dans l’Est du Bassin Parisien, à la limite des départements de la Meuse et de la Haute-Marne. A l’échelle du secteur d’étude, le COx constitue une couche homogène d’environ 130 mètres d’épaisseur, profonde de 500 mètres en moyenne, encadrée par deux formations calcaires, l’Oxfordien au sommet et le Dogger à la base. Le COx présente des perméabilités très faibles et des propriétés de confinement favorables pour un stockage.Les gaz rares (He, Ne, Ar, Kr et Xe) sont chimiquement inertes, leur couche de valence étant saturée, aucune liaison covalente intramoléculaire n’est généralement possible. De plus, ils possèdent de nombreux isotopes, d’origine différente, ce qui fait d’eux d’excellents traceurs en hydrogéologie. Les concentrations en gaz rares dans les environnements sédimentaires sont contrôlées par la loi de Henry : ils se dissolvent dans l’eau avec laquelle ils sont en contact, et ce en fonction de paramètres tels que la température, la salinité et la pression.Afin de compléter et préciser les propriétés du COx dans une zone de 250 km² autour du Laboratoire souterrain de Meuse/Haute-Marne, appelée « zone de transposition » (ZT), l’Andra a entrepris une campagne de forages entre Novembre 2007 et Juin 2008. Dans le cadre de cette campagne, le COx a été carotté dans quatre forages et échantillonné. L’un des forages a également recoupé l’ensemble de la pile sédimentaire Mésozoïque, depuis l’Oxfordien calcaire jusqu’à la base du Trias (-1600 mètres).Sur les quatre forages de la zone de transposition (A, B, C et D), des échantillons de roches ont été prélevés et conditionnés pour l’analyse en laboratoire des concentrations en gaz rares dissous dans les eaux porales. Les concentrations absolues en gaz rares ont été déterminées par spectrométrie de masse.Les profils en He obtenus pour chaque plateforme de forage présentent la même tendance. Les concentrations en He mesurées dans les eaux porales de la plateforme C sont en moyenne entre 2 et 3 fois plus faibles que pour les autres plateformes, et ainsi comparables aux valeurs mesurées dans le laboratoire souterrain, ce qui suggèrerait une circulation des eaux dans le Dogger comparativement moins lente que dans les autres plateformes de forage. Une modélisation 1-D des profils de concentration en He a permis de valider les mesures analytiques et de confirmer que la forme des profils est contrôlée par les concentrations en He imposées dans le Dogger. Le profil de concentrations en He mesurées dans le forage profond suggère d’une part une influence très faible voire nulle d’un flux d’origine mantellique et d’autre part une isolation des formations triasiques et du Lias adjacent. L’ensemble des résultats obtenus a ainsi permis d’avoir une meilleure connaissance des processus de transferts diffusifs dans la formation du COx et dans les aquifères encaissants<br>The French Radioactive Waste Management National Agency (Andra) is studying the possibility of a high level and long lived radioactive waste repository in geological formation. Since 1994, Andra is studying the properties of the Callovo-Oxfordian (COx) argillaceous rock, located in the eastern part of the Paris Basin. In the designated zone, COx is a 130 meters thick clay rich sequence, found at a depth of about 500 meters and encompassed between two aquifers, the Oxfordian limestone above and the Dogger limestone below. Callovo-Oxfordian permeabilities are very low, which is suitable with radioactive waste disposal. Noble gases (He, Ne, Ar, Kr and Xe) are considered as natural tracers, useful in hydrogeology, for several reasons. First, noble gases are nearly chemically inert, and then no reaction occurs between them and other species. Secondly, noble gases have several isotopes and many of them have different origins, so it is possible to distinguish sources terms. Noble gases concentrations in geological formations are controlled by physical properties such as temperature, pressure and salinity. To have more information on the COx properties, Andra has selected four drilling sites in a 250 km2 area around the Underground Research Laboratory. From November 2007 to June 2008, on each site, Callovo-Oxfordian clay and both overlaying (Oxfordian) and underlying (Dogger) limestones were investigated. A 1600 meters deep borehole, reaching the Trias base, allows investigating the whole length of the Mesozoïc sedimentary pile.On each drilling sites (named A, B, C and D), pore water noble gases concentrations were performed by mass spectrometry. Each helium profiles show the same general trends. Helium concentrations measured in the borehole C COx pore water are about 2 to 3 times lower than those observed for the other boreholes, and so comparable with previous measurements in the Underground Laboratory. These lower concentrations for borehole C could suggest differences in water average velocities in Dogger limestone, in comparison with the other ones. Calculations using a 1-D model were done; the results corroborate analytical measurements and confirm that helium diffusion profiles in the COx are controlled by Dogger helium concentrations that were put in the model. The vertical profile of dissolved helium concentration throughout the deep borehole suggest on the one hand that there is no deep crustal flux, and on the other hand that Trias is well isolated from the Lias and Dogger overlaying formations.The whole results obtained in this study provide a better understanding about diffusive transfer processes occurring in the COx and in the surrounding limestone aquifers

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Stanley, Rachel H. R. "A determination of air-sea gas exchange and upper ocean biological production from five noble gasses and tritiugenic helium-3." Thesis, Massachusetts Institute of Technology, 2007. http://hdl.handle.net/1721.1/42282.

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Thesis (Ph. D.)--Joint Program in Chemical Oceanography (Massachusetts Institute of Technology, Dept. of Earth, Atmospheric, and Planetary Sciences; and the Woods Hole Oceanographic Institution), 2007.<br>Includes bibliographical references (p. 215-225).<br>The five noble gases (helium, neon, argon, krypton, and xenon) are biologically and chemically inert, making them ideal oceanographic tracers. Additionally, the noble gases have a wide range of solubilities and molecular diffusivities, and thus respond differently to physical forcing. Tritium, an isotope of hydrogen, is useful in tandem with its daughter helium-3 as a tracer for water mass ages. In this thesis, a fourteen month time-series of the five noble gases, helium-3 and tritium was measured at the Bermuda Atlantic Time-series Study (BATS) site. The time-series of five noble gases was used to develop a parameterization of air-sea gas exchange for oligotrophic waters and wind speeds between 0 and 13 m s-1 that explicitly includes bubble processes and that constrains diffusive gas exchange to ± 6% and complete and partial air injection processes to ± 15%. Additionally, the parameterization is based on weeks to seasonal time scales, matching the time scales of many relevant biogeochemical cycles. The time-series of helium isotopes, tritium, argon, and oxygen was used to constrain upper ocean biological production. Specifically, the helium flux gauge technique was used to estimate new production, apparent oxygen utilization rates were used to quantify export production, and euphotic zone seasonal cycles of oxygen and argon were used to determine net community production. The concurrent use of these three methods allows examination of the relationship between the types of production and begins to address a number of apparent inconsistencies in the elemental budgets of carbon, oxygen, and nitrogen.<br>by Rachel H.R. Stanley.<br>Ph.D.

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Johnson, Christine Michelle. "Examination of natural background sources of radioactive noble gases with CTBT significance." Thesis, 2013. http://hdl.handle.net/2152/23631.

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For verifying the Comprehensive Nuclear-Test-Ban Treaty (CTBT), different monitoring technologies (seismic, infrasound, hydroacoustic, and radionuclide detection) are combined. The monitoring of radioactive xenon isotopes is one of the principal methods for the determination of the nuclear nature of an explosion. After an underground nuclear detonation the radioxenon isotopes [superscript 131m]Xe, [superscript 133m]Xe, ¹³³Xe, and ¹³⁵Xe, and the radioargon isotope ³⁷Ar have an increased probability of detection. In order to effectively utilize these isotopes as indicators of nuclear testing, an accurate background must be calculated. This work examines the fission products produced by spontaneous fission of ²³⁸U, which is naturally present in the earth's crust, and of ²⁴⁰Pu which is present as a product of nuclear weapons and nuclear reactor accidents. These calculations provide a range of production values for radioxenon in a variety of geologies as well as at various historic locations. The activation of geologic calcium and potassium by cosmic ray neutrons is considered for a variety of properties effecting the neutron flux. These calculations provide a range of radioargon production values across a selection of geologies. The impact of latitude and the solar activity cycle are also examined. In order to examine the transport of the isotopes through soil a model of the transport of xenon and argon through various geologies was developed. This model incorporates both the introduction of xenon from the atmosphere and that produced by spontaneous fission. This is then considered in light of what might be observed in an on-site inspection (OSI). What this work finds is that the radioxenon natural background does exceed detection limits in particular locations and geologies, however, a careful examination of the location and the ideal sampling depths can minimize the impact during an OSI. Radioargon, however, has a much larger natural background at shallow depths which are the realm of OSI sampling. Should radioargon sampling be used in an OSI the sampling time is crucial in distinguishing a nuclear explosion from the natural background. In some scenarios the natural background production of radioargon may be sufficient to interfere with the detection of an underground nuclear weapon test. This information may be beneficial in the development of future OSI noble gas monitoring techniques.<br>text

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Stanley, Rachel H. R. "A determination of air-sea gas exchange and upper ocean biological production from five noble gases and tritiugenic helium-3." 2007. http://hdl.handle.net/1912/2029.

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Thesis (Ph. D.)--Massachusetts Institute of Technology and Woods Hole Oceanographic Institution, 2007.<br>"September 2007". "Joint Program in Oceanography/Applied Ocean Science and Engineering"--Cover. Title from Web page (viewed on Mar. 24, 2008). Includes bibliographical references (p. 215-225).

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Books on the topic "Radioactive gages"

1

Golʹdin, M. L. Teoreticheskie osnovy izmeritelʹnoĭ tekhniki fotonnogo izluchenii͡a︡. Ėnergoatomizdat, 1985.

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Urbański, Piotr. Application, manufacturing, and trends in development of nucleonic gauges in Poland. Institute of Nuclear Chemistry and Technology, 1998.

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A, Izraėlʹ I͡U, and Gosudarstvennyĭ komitet SSSR po gidrometeorologii i kontroli͡u prirodnoĭ sredy., eds. I͡Aderno-fizicheskie metody analiza v kontrole okruzhai͡ushcheĭ sredy: Trudy III vsesoi͡uznogo soveshchanii͡a, Tomsk, 21-23 mai͡a 1985 g. Gidrometeoizdat, 1987.

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Prudic, David E. Tritium and radioactive carbon (. U.S. Dept. of the Interior, U.S. Geological Survey, 1995.

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Consultants, Meeting on Isotopes of Noble Gases as Tracers in Environmental Studies (1989 Vienna Austria). Isotopes of noble gases as tracers in environmental studies: Proceedings of a consultants meeting on isotopes of noble gases as tracers in environmental studies organized by the International Atomic Energy Agency and held in Vienna from 29 May to 2 June 1989. International Atomic Energy Agency, 1992.

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Müller, W. Produktion und Verbleib von Gasen im Grubengebäude eines salinaren Endlagers: Statusbericht. GSF-Forschungszentrum für Umwelt und Gesundheit, 1991.

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Sasidharan, N. Sathi. Development of transition metal oxide catalysts for treatment of off-gases released during pyrolysis of organic ION exchange resins. Bhabha Atomic Research Centre, 2005.

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United States. Dept. of Energy. Office of Nuclear Safety. Report on the handling of safety information concerning flammable gases and ferrocyanide at the Hanford waste tanks. U.S. Dept. of Energy, Office of Nuclear Safety, 1990.

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Safety, United States Dept of Energy Office of Nuclear. Report on the handling of safety information concerning flammable gases and ferrocyanide at the Hanford waste tanks. U.S. Dept. of Energy, Office of Nuclear Safety, 1990.

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United States. Dept. of Energy. Office of Nuclear Safety. Report on the handling of safety information concerning flammable gases and ferrocyanide at the Hanford waste tanks. U.S. Dept. of Energy, Office of Nuclear Safety, 1990.

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Book chapters on the topic "Radioactive gages"

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Owunwanne, Azuwuike, Mohan Patel, and Samy Sadek. "Radioactive noble gases." In The Handbook of Radiopharmaceuticals. Springer US, 1995. http://dx.doi.org/10.1007/978-1-4757-0414-3_13.

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Barton, Matt. "Wasteland: Hot, Mean, and Radioactive." In Vintage Games 2.0. A K Peters/CRC Press, 2019. http://dx.doi.org/10.1201/9780429280542-29.

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West, J. B., C. T. Dollery, and P. Hugh-Jones. "Pulmonary Gas Exchange Measurements Using Radioactive Gases." In Ciba Foundation Symposium - Pulmonary Structure and Function. John Wiley & Sons, Ltd., 2008. http://dx.doi.org/10.1002/9780470719282.ch9.

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Barry, P. J. "The Use of Radioactive Tracer Gases to Study the Rate of Exchange of Water Vapor between Air and Natural Surfaces." In Isotope Techniques in the Hydrologic Cycle. American Geophysical Union, 2013. http://dx.doi.org/10.1029/gm011p0069.

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Tuniz, Claudio. "5. Radioactive gadgets and gauges." In Radioactivity. Oxford University Press, 2012. http://dx.doi.org/10.1093/actrade/9780199692422.003.0005.

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Bello, Igor. "Vacuum Gauges with Radioactive Emitters." In Vacuum and Ultravacuum. CRC Press, 2017. http://dx.doi.org/10.1201/9781315155364-25.

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"Behavior of Radioactive Aerosols and Gases." In Radioactive Air Sampling Methods. CRC Press, 2010. http://dx.doi.org/10.1201/b10261-10.

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Zalutsky, Michael R. "Radioactive Noble Gases for Medical Applications." In Radiotracers for Medical Applications. CRC Press, 2019. http://dx.doi.org/10.1201/9780429278785-2.

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FLORKOWSKI, T., and K. RÓZANSKI. "RADIOACTIVE NOBLE GASES IN THE TERRESTRIAL ENVIRONMENT." In The Terrestrial Environment, B. Elsevier, 1986. http://dx.doi.org/10.1016/b978-0-444-42225-5.50016-4.

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"Sampling Air for Argon-41, Krypton-85 and Other Gamma-Emitting Radioactive Gases Using Gamma-Spectroscopy." In Radioactive Air Sampling Methods. CRC Press, 2010. http://dx.doi.org/10.1201/b10261-31.

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Conference papers on the topic "Radioactive gages"

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Quercetti, Thomas, Andre Musolff, and Karsten Mu¨ller. "Instrumented Measurements on Radioactive Waste Disposal Containers During Experimental Drop Testing." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59142.

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In context with disposal container safety assessment of containers for radioactive waste the German Federal Institute for Materials Research and Testing (BAM) performed numerous drop tests in the last years. The tests were accompanied by extensive and various measurement techniques especially by instrumented measurements with strain gages and accelerometers. The instrumentation of a specimen is an important tool to evaluate its mechanical behavior during impact. Test results as deceleration-time and strain-time functions constitute a main basis for the validation of assumptions in the safety analysis and for the evaluation of calculations based on finite-element methods. Strain gauges are useful to determine the time dependent magnitude of any deformation and the associated stresses. Accelerometers are widely used for the measuring of motion i.e. speed or the displacement of the rigid cask body, vibration and shock events. In addition high-speed video technique can be used to visualize and analyze the kinematical impact scenario by motion analysis. The paper describes some selected aspects on instrumented measurements and motion analysis in context with low level radioactive waste (LLW) container drop testing.

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Polkanov, M. A., A. Eu Savkin, S. A. Dmitriev, et al. "Plasma Treatment of Radioactive Waste in Shaft Furnace." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1157.

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Abstract Moscow SIA RADON has developed and tested an experimental plant for treatment of radioactive waste of the mixed type including up to 40 wt. % of incombustible components with the capacity from 50 to 80 kg/h on the base of the shaft furnace with plasma heat source. Heating furnace was provided due to the arc DC plasma torch with electric capacity from 60 to 150 kW, designed at RADON. The expenses of the electric power for plasma torch were 0.5 up to 1.5 kWh/1 kg of waste depending on their composition. Pyrolytic gas with calorific value up to 4.5–5.5 MJ/kg at an output of the furnace was received, which burning provided a necessary temperature mode in the afterburner. In the shaft furnace the mode impeding radionuclides loss with off-gases has been realized. The ablation of 137Cs from the furnace did not exceed 12%, 60Co – 2.5% and trans-uranium elements – 1% due to the shaft operation mode chosen. The treatment of radioactive waste without fluxing additives has been carried out, and the slag compound with high chemical durability has been obtained.

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"On the possibility to detect some radioactive noble gases by Cherenkov counting of polycarbonates." In 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference (2013 NSS/MIC). IEEE, 2013. http://dx.doi.org/10.1109/nssmic.2013.6829495.

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Tian, Lifang, Mingfen Wen, and Jing Chen. "Treatment and Disposal of the Radioactive Graphite Waste." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29985.

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A large number of nuclear reactors with graphite as moderator and reflector material are facing to be decommissioned now or later, and the radioactive graphite waste is a large part of the involved wastes. In addition, high temperature gas-cooled reactors being developed rapidly use a large quantity of graphite material (up to 95%) in the nuclear fuel elements, besides graphite material as their moderator and reflector material in the reactor cores. Therefore, it is very critical to manage these graphite wastes from the decommissioned and being decommissioned reactors. The part with low-level radioactive contamination that could not be reused now, may be disposed of as solid waste to reduce its volume, and the possibility of its being retrieved and reused in the future with advanced technology should be considered. The other graphite waste with high-level radioactive contamination requires much more consideration. Due to several factors, such as its large quantity, a lack of available disposal sites and public acceptance, it may not be disposed of directly in the repository any more. An option may be the transformation of the high-level radioactive graphite waste into low-level radioactive waste through physical and chemical processes. The current technologies involve, e.g., thermal treatment to release 36Cl, capture of the 14C from the gases of incineration of carbon material and decomposition of carbon dioxide into solid carbon. After these treatments the carbon material might be decontaminated and separated as low-level radioactive waste and a small amount of residual high-level waste could be disposed of ultimately. In order to achieve a sustainable development of graphite material, the maximum utility and the minimal disposal of radioactive graphite should be considered in the management of radioactive graphite waste. It is urgent to explore new technologies for decontaminating and recycling radioactive graphite.

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Chambers, A. V., W. R. Rodwell, M. Kelly, A. R. Hoch, and A. J. Baker. "Assessment of Package Performance During Long-Term Storage of Intermediate-Level Radioactive Waste." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4517.

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In the UK, the need for the long-term management of intermediate-level radioactive wastes arises from the absence of an established deep disposal option. As a consequence there is a requirement to demonstrate the ‘passive safety’ of waste packages in stores over a necessarily lengthy period (perhaps 150 years or more). ‘Passive safety’ is taken here to imply that the waste packages themselves would remain safe without intervention; it is assumed however, that the store building and associated infrastructure would need to be actively maintained and that the store may need to be ventilated. Importantly, methods for waste storage also need to ensure that possible future options for disposal are not foreclosed. An extended period of storage suggests that emphasis will need to be placed by waste producers on understanding a number of issues such as: • the impact of corrosion on container integrity; • the assessment of container vents and other features as a pathway for the release of radioactivity; • the extent to which wastes are conditioned for storage and the selection of appropriate methods; • the generation and behaviour of toxic or flammable gases in the storage facility; and the mitigating steps that might be needed to address adverse impacts (e.g. the type of ventilation that the store requires). In this paper, we review the requirements and current state of knowledge relevant to the assessment of operational releases of radioactive, flammable and toxic gases from wastes in long-term interim storage.

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Suckling, Paul, Nicola Calder, Paul Humphreys, Fraser King, and Helen Leung. "The Development and Use of T2GGM: A Gas Modelling Code for the Postclosure Safety Assessment of OPG’s Proposed L&ILW Deep Geologic Repository, Canada." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16291.

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As part of the postclosure safety assessment of Ontario Power Generation’s (OPG’s) proposed Deep Geologic Repository (DGR) for Low and Intermediate Level Waste (L&ILW) at the Bruce site, Ontario, a Gas Generation Model (GGM) has been developed and used to model the detailed generation of gas within the DGR due to corrosion and microbial degradation of the organics and metals present. The GGM is based on a kinetic description of the various microbial and corrosion processes that lead to the generation and consumption of various gases. It takes into account the mass-balance equations for each of the species included in the model, including three forms of organic waste (cellulose, ionexchange resins, and plastics and rubbers), four metallic waste forms and container materials (carbon and galvanised steel, passivated carbon steel, stainless steel and nickel-based alloys, and zirconium alloys), six gases (CO2, N2, O2, H2, H2S, and CH4), five terminal electron acceptors (O2, NO3−, Fe(III), SO42−, and CO2), five forms of biomass (aerobes, denitrifiers, iron reducers, sulphate reducers, and methanogens), four types of corrosion product (FeOOH, FeCO3, Fe3O4, and FeS), and water. The code includes the possibility of the limitation of both microbial and corrosion reactions by the availability of water. The GGM has been coupled with TOUGH2 to produce T2GGM; a code that models the generation of gas in the repository and its subsequent transport through the geosphere. T2GGM estimates the peak repository pressure, long time repository saturation and the total flux of gases from the geosphere. The present paper describes the development of T2GGM and the numerical modelling work undertaken to calculate the generation and build-up of gas in the repository, the two-phase exchange of gas and groundwater between the repository and the surrounding rock, and between the rock and the surface environment. The results have been used to inform the safety assessment modelling.

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Needham, Michael. "Detecting Sources of Ionizing Radiation in the Waste Stream." In 10th Annual North American Waste-to-Energy Conference. ASMEDC, 2002. http://dx.doi.org/10.1115/nawtec10-1016.

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Why is the detection of radioactive sources important to the solid waste industry?: Radioactive material is used extensively in the United States in research, medicine, education, and industry for the benefit of society (e.g. smoke detectors, industrial process gauges, medical diagnosis/treatment). Generally speaking, the Nuclear Regulatory Commission and state governments regulate the use and disposal of radioactive materials. Licensed radioactive waste disposal facilities receive the bulk of the waste generated in the United States with exceptions for low-level waste (e.g. medical patient waste) that may be disposed of as municipal waste. According to the Conference of Radiation Control Program Directors, Inc (CRCPD)., there has been an increasing number of incidence involving the detection of prohibited radioactive wastes at solid waste management facilities. While the CRCPD acknowledges that the increased incidence may be partially attributed to the growing number of solid waste facilities that have detection systems, undetected sources of ionizing radiation can harm the environment, have a negative impact on employee health and safety, and result in significant remedial actions. Implementing an effective detection/response plan can aid in the proper management of radioactive waste and serve to minimize the potential for negative outcomes.

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Bilheux, J. C. "Simulation of the effusive-flow of reactive gases in tubular transport systems: Radioactive ion beam applications." In The CAARI 2000: Sixteenth international conference on the application of accelerators in research and industry. AIP, 2001. http://dx.doi.org/10.1063/1.1395305.

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Leduc, Daniel R., and Allen C. Smith. "Survey of Packaging Requirements for the Transport of Highly Hazardous Materials." In ASME 2003 Pressure Vessels and Piping Conference. ASMEDC, 2003. http://dx.doi.org/10.1115/pvp2003-2132.

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Among hazardous materials those which are most dangerous fall into three categories: chemical, biological, and radioactive. The DOT hazard classes for these three categories are Hazard Class 2.3 (poisonous gases) and 6.1 (toxic substances) for chemical hazards, Hazard Class 6.2 (infectious substances) for biological hazards and Hazard Class 7 for radioactive material (RAM) hazards. The packaging requirements for chemical and biological hazards are outlined and compared with RAM packaging requirements. RAM packages are found to be able to withstand much more severe performance tests than packages for other, more lethal hazards.

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Stevens, Howard, and Gerard Laurent. "Treatment of Irradiated Graphite From French Bugey Reactor." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96167.

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In 2008, following the general French plan for nuclear waste management, Électricité de France attempted to find for irradiated graphite an alternative solution to direct storage at the low-activity long-life storage center in France managed by the national agency for wastes (ANDRA). EDF management requested that its engineering arm, EDF CIDEN, study the graphite treatment alternatives to direct storage. In mid-2008, this study revealed the potential advantage for EDF to use a steam reforming process known as THermal Organic Reduction, “THOR” (owned by Studsvik, Inc., USA), to treat or destroy the graphite matrix and limit the quantity of secondary waste to be stored. In late 2009, EDF began a test program with Studsvik to determine if the THOR steam reforming process could be used to destroy the graphite. The program also sought to determine if the graphite could be treated to release the bulk of activity while minimizing the gasification of the bulk mass of the graphite. In October 2009, tests with non-irradiated graphite were completed and demonstrated destruction of a graphite matrix by the THOR process at satisfactory rates. After gasifying the graphite, focus shifted to the effect of roasting graphite at high temperatures in inert gases with low concentrations of oxidizing gases to preferentially remove volatile radionuclides while minimizing the graphite mass loss to 5%. A radioactive graphite sleeve was imported from France to the US for these tests. Completed in April 2010, ‘Phase I’ of testing showed that the process removed >99% of H-3 and 46% of C-14 with <6% mass loss. Completed in September 2011, ‘Phase II’ testing achieved increased removals as high as 80% C-14. During Phase II, it was also discovered that roasting in a reducing atmosphere helped to limit the oxidation of the graphite. Future work seeks to explore the effects of reducing gases to limit the bulk oxidation of graphite. If the graphite could be decontaminated of long-lived radionuclides up to 95% for C-14 while minimizing mass loss to <5%, this would minimize the volume of any secondary waste streams and potentially lower the waste class of the larger bulk of graphite. Alternatively, if up to 95% decontamination of C-14 is achieved, the graphite may be completely gasified which could result in lower disposal volumes.

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Reports on the topic "Radioactive gages"

1

Yim, M. S., and S. A. Simonson. Generation and release of radioactive gases in LLW disposal facilities. Office of Scientific and Technical Information (OSTI), 1995. http://dx.doi.org/10.2172/95643.

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Welch, K. M., L. A. Smart, and R. J. Todd. Enhanced Ignition of Cold Cathode Gauges Through the Use of Radioactive Isotopes. Office of Scientific and Technical Information (OSTI), 1995. http://dx.doi.org/10.2172/1119390.

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Sherwood, D. J. Action plan for response to abnormal conditions in Hanford high level radioactive liquid waste storage tanks containing flammable gases. Revision 1. Office of Scientific and Technical Information (OSTI), 1994. http://dx.doi.org/10.2172/10149511.

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Benac, D. J., and W. R. Schick. Sealed source and device design safety testing. Volume 5: Technical report on the findings of Task 4, Investigation of failed radioactive stainless steel troxler gauges. Office of Scientific and Technical Information (OSTI), 1995. http://dx.doi.org/10.2172/137424.

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Distribution of gases in the unsaturated zone at a low-level radioactive-waste disposal site near Sheffield, Illinois. US Geological Survey, 1988. http://dx.doi.org/10.3133/wri884025.

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